ML20035D696
| ML20035D696 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/16/1992 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9304140011 | |
| Download: ML20035D696 (5) | |
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'o UNITED STATES y
4,7 NUCLEAR REGULATORY COMMISSION 3
e ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 8
o WASHINGTON, D. C. 20555
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l October 16, 1992 MEMORANDUM FOR:
James M. Taylor Executive Director for Operations ATTN:
J.
Blaha FROM:
R F.
ra ey utive Director, ACRS
SUBJECT:
389TH ACRS MEETING FOLLOW-UP ITEMS Attached is a summary of the Actions, Agreements, Requests, and Commitments made during the 389th ACRS Meeting, September 10-12, 1992.
Attachment:
As stated cc w/ attachment:
E.
L.
Jordan, AEOD R.
M.
Bernero, NMSS T.
E. Murley, NRR E.
S.
Beckjord, RES S.
Chilk, SECY J.
Johnson, OCM/IS J.
Scarborough, OCM/KR K.
Connaughton, OCM/JC J.
Guttmann, OCM/FR E.
McKenna, OCM/GdeP i
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SUMMARY
OF ACTIONS, AGREEMENTS, REQUESTS, AND COMMITMENTS I'
i 389TH ACRS MEETING SEPTEMBER 10-12, 1992 During its 389th meeting, September 10-12, 1992, the Advisory Committee on Reactor Safeguards discussed several matters and l
completed the reports and memoranda as noted.
[
REPORTS f
e Dicital Instrumentation and Control System Reliability I
i (Report to Chairman Selin, dated September 16, 1992) l i
NRC Staff's Procosed Resolution of Issues in its Evaluation of e
Shutdown and Low-Power Operations (Report to Mr. James M.
Taylor, Executive Director for Operations, dated September 15, 3
1992) l e
Draft Commission Paper. "Desion Certification and Licensinc Policy Issues Pertainina to Passive and Evolutionary Advanced 1
Licht Water Reactor Desions." (Report to Mr. James M. Taylor,
[
Executive Director for Operations, dated September 15, 1992) e General Electric Nuclear Enercy Power Ucrate Procram/ Fermi.
Unit 2 Power Increase Recuest (Report to Mr. James M. Taylor, Executive Director for Operations, dated September 17, 1992)
MEMORANDUM g
J e
Proposed Generic Letter on Analoc-To-Dicital Replacements Under 10 CFR 50.59 Rule (Memorandum for Thomas E.
- Murley, l
Director of Office of Nuclear Reactor Regulation, from Raymond F. Fraley, Executive Director of the ACRS, dated September 17, 1992)
ANTICIPATED ACRS ACTIVITIES j
The Committee agreed to discuss the following during its 389th i
meeting, October 8-10, 1992-A.
Environmental Oualification of Safetv-Grade Dicital Computer 3
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Protection and Control Systems - Review and comment on the NRC research ef fort on environmental qualification of safety-grade l
digital computer protection and control systems.
Representa-tives of the NRC staff and the nuclear industry will participate, as appropriate.
B.
Use of Probabilistic Risk Assessment in the Reculatory Process i
3
- Briefing by and discussion with representatives of the NRC staff regarding the use of PRA by the NRC staff in the t
regulatory process.
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C.
Yankee Rowe Nuclear Station-Reactor Pressure Vessel l
Embrittlement Briefing by and discussion with j
representatives of the NRC staff regarding lessons learned from the NRC staff's review of the reactor pressure vessel i
embrittlement issue at the Yankee Rowe Nuclear Power Station.
Representatives of the licensee will participate, as
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appropriate.
D.
Format and Content of Desian Certification Applications -
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Review and comment on SECY-92-287, " Form and Content for a Design Certification Rule," for standardized nuclear power i
plant designs.
Representatives of the NRC staff and the l
nuclear industry will participate, as appropriate.
E.
Branch Technical Position on Eguipment Oualification for i
License Renewal - Review and comment on Branch Technical l
Position regarding qualification of electrical equipment for nuclear power plant license renewal.
Representatives of the l
NRC staff and the nuclear industry will participate, as appropriate.
F.
Operator Training and Recualification Briefing and discussion regarding the results of the pilot simulator i
examination program, and proposed changes to 10 CFR Part 55 requirements for requalification examinations.
i Representatives of the NRC staff and the nuclear industry will l
participate, as appropriate.
G.
Maintenance of Nuclear Power Plants - Review and comment on the proposed NRC Regulatory
- Guide,
" Monitoring the j
Effectiveness of Maintenance at Nuclear Power Plants," for 1
implementation of the Maintenance Rule and an associated l
NUMARC document.
Representatives of the NRC staff and the l
nuclear industry will participate, as appropriate.
H.
Stability of Boilina Water Reactors - Review and comment on proposed resolution of core power stability issues in GE boiling water reactors.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
4 I.
Desian Acceptance Criteria Review and report on Design Acceptance Criteria in the areas of man-machine interface and 7
control and protection systems.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate, t
J.
NRC Staff Review of ITAAC for,the GE ABWR - Discuss proposed ACRS report on the process for the NRC staff's review of the Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the ABWR design.
Representatives of the NRC staf f and the nuclear industry will participate, as appropriate.
1 K.
Resolution of ACRS Comments and Recommendations Discuss response from NRC Executive Director for Operations regarding NRC staff reaction to ACRS comments and recommendations.
l Summarv/ List of Follow-up and Other Matters l
Dr. Murley agreed to provide the Committee with a copy of the j
analysis the staff has performed of the similarities and
4 differences between the Maintenance and License Renewal Rules.
(Mr. Alderman is the cognizant engineer on this matter.)
The Committee recommended that whenever the industry or staff e
plans to discuss the results of calculations performed by a computer code that the Committee has not reviewed, advance notice should be given and the code documentation should be made available to the Committee, if necessary, before the presentation.
This recommendation was included in the Committee's report on the GE power uprate program / Fermi-2.
(Dr. Savio is the cognizant engineer on this matter.)
e The Safety Goal Subcommittee should meet to develop suggestions to the Commission on how the Safety goal might be used to:
a)
Develop an agreement in principle on the interpretation of Safety Goals in terms of surrogates and level of confidence.
b)
Specific application of the Safety Goals to determine unnecessary regulations.
(Mr. Houston is the cognizant engineer on this matter.)
e The Planning and Procedures Subcommittee will review the present background material and look further into developing recommendations with regard to sending draft / preliminary documents to the Public Document Room at the same time they are sent to the ACRS for review.
(Mr. Fraley is the cognizant engineer on this matter.)
The ACRS Office should transmit a copy of a guide " Procedures e
for Presentations to ACRS Subcommittees and the Full Committee" to the staff for use in making presentations. (Mr.
Fraley is the cognizant engineer on this matter.)
Note:
This Guide was forwarded to you, by memorandum from me, dated October 6, 1992.
The Committee confirmed its interest in having an opportunity e
to review the proposed final version of a generic letter on analog-to-digital safety system replacements.
S.
- Newberry, NRR, was informed of this request.
Note:
This request was sent to Thomas E.
- Murley, by memorandum from me, dated September 17, 1992.
The ACRS Plan of Action to provide advice regarding use of the safety goal to determine where unnecessary regulations exist was put on hold until after the Committee discusses the revised Regulatory Analysis Guidelines. (Mr. Houston is the cognizant engineer on this matter.)
Note:
This matter is scheduled for consideration during the 391st ACRS meeting (November 5-7, 1992).
The Committee discussed the manner by which uncertainty should e
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be reflected in use of the safety goals.
They further agreed that a meeting should be held involving some ACRS members and senior managers (Directors) of NRR/RES/EDO offices to develop j
an interpretation of the safety goals in terms of surrogates and confidence levels. (Mr Houston is the cognizant engineer j
on this matter.)
The Committee agreed to the immediate assignment of new chairmen for the 6 Subcommittees that are needed as a result i
of D. Wards departure from the Committee in November 1992, as 3
i follows:
Advanced Reactor Designs - Dr. Wilkins e
Containment Systems - Dr. Catton o
Decay Heat Removal Systems - Dr. Catton e
Planning and Procedures - Dr. Shewmon e
Plant License Renewal - Dr. Kress e
The Committee agreed that Mr. Lindblad be assigned as the new Chairman for the Extreme External Phenomena and the
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Reliability and Quality subcommittees.
e Dr.
Shewmon reported that he had obtained additional i
information by meeting with the staff and suggested that the 4
following matters be dropped at this time with regard to staf f l
and industry briefings of the Committee:
e Reactor pressure vessel upper head cracks observed in a
some European nuclear power plants and whether such problems might occur in U.S.
reactors.
i The NRC Augmented Inspection Team's investigation of the e
November 6, 1991 event that occurred at Millstone, Unit j
2, involving failure of a moisture separator reheater drain line elbow.
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